Journal of the Korean Chemical Society (대한화학회지)

Korean Chemical Society (대한화학회)
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Separation of Fission Product Elements from Synthetic Dissolver Solutions of Spent Pressurized Water Reactor Fuels by $TBP/XAD-16/HNO_3$Extraction Chromatography

$TBP/XAD-16/HNO_3$추출 크로마토그래피에 의한 모의 사용후핵연료 용해용액 중 미량 핵분열생성물 원소의 분리

  • Lee, Chang Heon (Korea Atomic Energy Research Institute, Nuclear Chemistry Research Team) ;
  • Choi, Kwang Soon (Korea Atomic Energy Research Institute, Nuclear Chemistry Research Team) ;
  • Kim, Jung Suk (Korea Atomic Energy Research Institute, Nuclear Chemistry Research Team) ;
  • Choi, Ke Chon (Korea Atomic Energy Research Institute, Nuclear Chemistry Research Team) ;
  • Jee, Kwang Yong (Korea Atomic Energy Research Institute, Nuclear Chemistry Research Team) ;
  • Kim, Won Ho (Korea Atomic Energy Research Institute, Nuclear Chemistry Research Team)
  • 이창헌 (한국원자력연구소 원자력화학연구팀) ;
  • 최광순 (한국원자력연구소 원자력화학연구팀) ;
  • 김정석 (한국원자력연구소 원자력화학연구팀) ;
  • 최계천 (한국원자력연구소 원자력화학연구팀) ;
  • 지광용 (한국원자력연구소 원자력화학연구팀) ;
  • 김원호 (한국원자력연구소 원자력화학연구팀)
  • Published : 20010800
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Abstract

A study has been carried out on the extraction chromatographic separation of fission products from spent pressurized water reactor (PWR) fuels for inductively coupled plasma atomic emission spectrometric analysis. Impregnation capacity of tri-n-butyl phosphate (TBP), which is well known as an extractant in the field of uranium separation from various nuclear grade materials, on Amberlite XAD polymeric macroporous support materials was measured. Amberlite XAD-16 of which the surface area is the highest was selected as a support material because its TBP impregnation capacity was the largest in Amberlite XADs. Sorption behaviour of this TBP impregnated resin was investigated for the fission product elements using acidic solutions simulated for dissolver solutions of spent PWR fuels. The parameters affecting the performance of the separation system were optimized. The fission product elements studied excluding Pd and Ru were quantitatively recovered with the precision of less than 3.1%.

경수로 사용후 핵 연료에 미량 함유되어 있는 핵분열생성물을 유도 결합 플라스마 원자방출분광법(ICP-AES)으로 분석하기 위하여 우라늄으로부터 학분열생성물을 추출 크로마토그래피로 분리, 회수하는 방법을 검토하였다. 우라늄 분리 분야에서 잘 알려져 있는 tri-n-butyl phosphate(TBP)를 추출제로 사용하여 몇 가지 Amberlite XAD 다공성 수지들에 대한 침윤능을 비교한 후 TPB침윤양이 가장 큰 Amberlite XAD-16을 지지체로 선택하였다. 사용후핵연료 용해용액과 화학조성이 유사한 모의 사용후핵연료 용해용액을 사용하여 TBP 침윤수지에 대한 핵분열생성물 원소들의 흡착거동을 조사하고, 분리에 미치는 여러 변수들을 최적화 하였다. Pd 및 Ru을 제외한 대부분의 핵분열생성물 원소들을 정밀도 3.1% 이하의 범위에서 정량적으로 회수할 수 있었다.

Keywords

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